ML20035F134
| ML20035F134 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 04/13/1993 |
| From: | Mendonca M Office of Nuclear Reactor Regulation |
| To: | Gemlich D UTAH, UNIV. OF, SALT LAKE CITY, UT |
| References | |
| NUDOCS 9304200308 | |
| Download: ML20035F134 (40) | |
Text
- _ _ _ _ _ _ - _ _ _
i April 13, 1993 l
Docket No. 50-407 Dr. Dietrich K. Gemlich 2202 MEB University of Utah Salt Lake City, Utah 84112
Dear Dr. Gemlich:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR REVISION OF THE EMERGENCY PLAN We are continuing our review of the University of Utah Emergency Plan, Revision 2 that you submitted by letter of September 21, 1992. During our review of your application, additional questions have arisen for which we require additional information and clarification.
Please provide response to the enclosed Request for Additional Information within 60 days of the date of this letter.
Following receipt of the additional information, we will continue our evaluation of your application. Also, we have attached, to the Request for Additional Information, guidance which you may find useful in your response to our request.
If you have any questions, please contact me at (301) 504-1128.
This request affects nine or fewer respondents and, therefore, is not subject to Office of Management and Budget review under Public Law 96-511.
Sincerely, Original signed by:
Marvin M. Mendonca, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION:[UTAHEPMM.WJE][Mendonca diskette]
Docket' Files.
BClayton PDRs MMendonca ONDD R/F OGC BGrimes ACRS (10)
SWeiss A. Bill Beach, RIV WEresian RErickson SW
- See previous concurrence ONDD:LA*
HOLB:RE*
ONDD:PM*
ONDO:D PEPB:BC*
BClayton WEresian MMendonca:lb SWeiss RErickson 04/13/93 04/13/93 04/13/93 4/p/93 04/13/93 f
l 9304200308 930413
/
PDR ADOCK 05000407 q, p g a n, :.m 7,
cc y F
PDR gj g y, y ;
.g,
gig
- ga RfC
%'o'%
/
UNITED STATES y
NUCLEAR REGULATORY COMMISSION
.E W ASHINGTON. D. C. 20555 E
/
April 13, 1993
- ...+
Docket No. 50-407 Dr. Dietrich K. Gemlich 2202 MEB University of Utah Salt Lake City, Utah 84112
Dear Dr. Gemlich:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR REVISION OF THE EMERGENCY PLAN We are continuing our review of the University of Utah Emergency Plan, Revision 2 that you submitted by letter of September 21, 1992. During our review of your application, additional questions have arisen for which we require additional information and clarification.
Please provide response to the enclosed Request for Additional Information within 60 days of the date of this letter.
Following receipt of the additional information, we will continue our evaluation of your application. Also, we have attached, to the Request for Additional Information, guidance which you may find useful in your response to our request.
If you have any questions, please contact me at (301) 504-1128.
This request affects nine or fewer respondents and, therefore, is not subject to Office of Management and Budget review under Public Law 96-511.
Sincerely,
~~
W-Marvin M. Mendonca, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page
University of Utah Docket Nos. 50-72/407 CC:
Mayor of Salt Lake City 451 South State Room 306 Salt Lake City, Utah 84111 Director Division of Radiation Control 1460 West 288 North P.O. Box 144850 Salt Lake City, Utah 84114-4850 Dr. Richard Koehn Office of the Vice President for Research 210 Park Building University of Utah Salt Lake City, Utah 84112 Dr. Gary M. Sandquist, Research Director of Nuclear Engineering Laboratory University of Utah Salt Lake City, Utah 84112 Dr. David M. Slaughter 3209 l'EB Mechanical Engineering Department University of Utah Salt Lake City, Utah 84112
Enclosure REQUEST FOR ADDITIONAL INFORMATION UNIVERSITY OF UTAH DOCKET NO. 50-407 1.
From the review of your submittal, we have confirmed that Revision 1 of your Emergency Plan was produced in 1980, prior to the issuance of currently available generic guidance (NUREG-0849 and Regulatory Guide 2.6 which are enclosed). As a result, Revision 2 of your Emergency Plan is not totally consistent with this generic guidance.
Therefore, we would encourage you to rewrite the Emergency Plan using the generic guidance documents, so that your emergency plans, particularly radiological emergency action guidelines, are more consistent with the generic guidance and with the emergency plans of other licensees.
Additionally, enclosed is a copy of another research reactor emergency plan that may provide some guidance in regard to form and style in your efforts.
2.
If you elect not to rewrite the plan, you should provide:
an indication of the changes to Revision 2 from Revision 1 and the a.
reasons for the change, b.
clarification of which table and figures are referenced in the plan.
The tables and figures in the text do not correspond to the tables and figures that are presented, e.g.,
in the definitions of Emergency Planning Zone and Site Boundary should it be figure 2 or 3 and where does the Appendix start?
in the definition of Emergency Procedures what is "EPL"?
under section 3.1, the first sentence refers to " Figure 4."
Should that be Figure I?
sections 7.4 and 8.1 refer to " Fig. 1."
Should that be Fig. 2? Section 7.4 also refers to " Figure 2" and should that be Figure 3?
3.
Regardless if the plan is rewritten or not:
Provide copies of the implementing procedures in your list titled a.
" University of Utah Nuclear Engineering Laboratory, Emergency Procedures by Title."
i
. b.
Provide the method you use to determine that you have reached the radiological " Classification Criteria" in Table 1,
- Radiological Criteria for Determining Emergency Class."
Clarify the definition of site boundary and university boundary.
In c.
Section 4 the use of atmospheric dispersion factor and other dose assessment parameters for site boundary seems to be those for the reactor room boundary (generic guidance would use the reactor room for site boundary).
d.
Additionally, the emergency action levels should be based on doses at the reactor room boundary, and the definition of site boundary is not consistent with this nor conservative in the section on Emergency Classification System. Assure that emergency classification system action levels are appropriate in that they are related to reactor room boundary conditions.
Define emergency control and related criteria that are referred to e.
in Section 7.4, first paragraph, last sentence.
f.
Clarify the areas with regard to organization and responsibilities.
For example, in the early phases of an emergency, it is not completely clear who is in charge.
(In Section 7.1, different entities are responsible for activation of the emergency organization and actual activation of the emergency support plan.)
Also, who has responsibility for authorizing a person to receive radiation levels above regulatory limits for life-saving or equipment protection activities. A final example is Figure I which is unclear in responsibility and authority versus communications functions.
g.
In Section 9, discuss if the "0EC" should also authorize recovery and reentry?
h.
The boundary for "EPZ" in Figure 2 should be explicitly defined.
- i. The emergency plan in the section on "EAls" has personnel emergencies, reactor emergencies and facility emergencies. These are not consistent with the four emergency classifications of Notification of Unusual Event (NOVE), Alert, Site Area Emergency, and General Emergency. Clarify the use and interface between the classifications, and provide guidance as to how the classification schemes are related.
- j. Assure that emergency personnel, in their capacity to communicate conditions to the NRC and others, clearly relate the classification to the NOUE, Alert, Site Area Emergency, and General Emergency.
For example, a fire under the plan may be classified as a facility emergency rather than a NOUE or other emergency classification depending on the potential hazard.
It should be clearly communicated to the NRC in terms of classification, i.e., NOUE, etc.
_3 k.
For fires, classification criteria as to duration, and location (related to magnitude of potential consequences) should be established consistent with potential consequences for the NOUE, etc.
1.
Provide discussion of emergency drills and exercises.
m.
In the maintenance of the emergency equipment and supplies, provide the criteria for calibration of radiation monitoring equipment.
Include frequency of periodic checks of the equipment.
~
1 NUREG-0849 N
Stanc'ard Review Plan for t7e Review and Evaluation of Emergency P!ans for Research and Test Reactors
$e'teIuN$hedfo'e1t br ![d Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement 5.S. Nuclear Regulatory Commission
/sshington, D.C. 20555 e
e
ABSTRACT This document provides a Standard Review Plan to assure that complete and uniform reviews are made of research and test reactor radiological emergency plans.
The report is organized under ten planning standards which correspond to the guidance criteria in American National Standard ANSI /ANS 15.16 - 1982 i
as endorsed by Revision I to Regulatory Guide 2.6.
The applicability of the items under each planning standard is indicated by subdivisions of the i
steady-state thermal power levels at which the reactors are licensed to operate.
Standard emergency classes and example action levels for research and l
test reactors which should initiate these classes are given in an Appendix.
i l
I I
1 l
e 4
l
~
t g
i I
iii
CONTENTS Pjgg AB5 TRACT............................................................
iii ACKNOWLEDGEMENT5....................................................
vii INTRODUCTION........................................................
1 CONTENT OF EMERGENCY PLAN............................................
3 AREAS OF REVIEW, PLANNING STANDARDS, AND EVALUATION ITEMS...........
5
1.0 INTRODUCTION
5
~
2.0 DEFINITIONS....................................................
6 3.0 ORGANIZATION AND RESP 0NSIBILITIES..............................
7 4.0 EMERGENCY CLASSIFICATION 5YSTEM................................
10 5.0 EMERGENCY ACTION LEVELS.........................................
12 6.0 EMERGENCY PLANNING 20NES.......................................
13 7.0 EMERGENCY RESP 0NSE.............................................
14 8.0 EMERGENCY FACILITIES AND EQUIPMENT.............................
17 9.0 REC 0VERY.......................................................
19 10.0 MAINTAINING EMERGENCY PREPAREDNESS.............................
20 APPENDIX I:
EMERGENCY CLASSES ACTION LEVELS AND PURP0SES.................,...............,.......................
23 APPENDIX II: ALTERNATE HETHOD FOR DETERMINING THE SIZE OF AN EMERGENCY PLANNING 20NE.............................
25 v
(
=
i i
I k
ACKNOWLEDGEMENT 5 The draft of this report was prepared with the assistance of the personnel of the Health Physics Technology Section, Rad clogi al ences
!K'2i;s; li !"'CD!it',."Is'r" OE's 'i' E'E'Ed 3 8 "**"'
for their technical contributions.
i This final revision was prepared after peer review and evaluation by a review committee consisting of members from the research and test reactor i
community. We wish to acknowledge D. M. Alger, University of Missouri, Columbia, W. J. Brynda, Brookhaven National Laboratory, L. Clark, Jr.,
Massachusetts Institute of Technology, D. E. Feltz, Texas A & M University,.
t A. G. Johnson, Oregon State University, and W. J. Richards, Argonne National i
Laboratory-West and Chairman of American Nuclear Society, ANS-15 Committee 1
for their valuable input to this document.
l i
i
)
i 1
k i
O vii
-y 4
-mi--sq q
m e-y3-ms+-
p w
pg,-g-q-gw-y,w b wenyt'74v me--*o'Fww-'
tpg'*-+wv"+Paf--dp
'tr-"*+r*---F"edet**'WM-t-'4 9 D
-M it'r y
STANDARD REVIEW PLAN FOR THE REVIEW AND EVALUATION OF EMERGENCY PLANS FOR RESEARCH AND TEST REACTORS INTRODUCTION j
Safety analyses for research and test reactors are based on the concept of a postulated Design Basis Event (DBE), an event for which the risk to the i
public health and safety is greater than that from any event that can be mechanistically postulated.
The rationale for using the DBE for research i
and test reactors is to assess the potential effects to the public health and safety and is based on the determination that the offsite doses from the DBE be within the requirements of 10 CFR Parts 20 and 100.
Consequently, if the requirements are met for a DBE condition, then the capability of the facility to withstand normal and abnormal operational transients and a broad spectrum of postulated credible accidents without undue risk to the public would also be defined within the DBE.
The postulated radioactive releases from credible accidents associated with the operation of research reactors will not result in offsite radio-logical doses to the general public exceeding the Protective Action Guides (PAGs) of I rem whole body or 5 rem thyroid.
Therefore, these facilities would not include the General Emergency class of accidents requiring Federal assistance as part of their emergency plan.
Pursuant to 10 CFR 50.54(q), each licensee who is authorized to possess and/or operate a research or test reactor under a license of the type specified in 10 CFR 50.21(c), shall follow and maintain in effect emergency plans which meet the requirements in Appendix E to 10 CFR Part 50.
Appendix E to 10 CFR Part 50, " Emergency Plans for Production and Utilization Faci-lities," establishes minimum requirements for emergency plans to attain an acceptable state of emergency preparedness and to provide reasonable assur-ante that protective measures can and will be taken to protect the health and safety of workers and the public.
Regulatory Guide 2.6 (Rev.1, March 1983) " Emergency Planning for Research and Test Reactors," which is specified by Appendix E as the guid-ante to be used to determine the acceptability of research and test reactor radiological emergency plans, describes a method acceptable to the NRC staff for complying with the Commission's emergency planning regulations.
Revi-sion 1 to Regulatory Guide 2.6 (dated March 1983), endorses American National Standard, ANSI /ANS-15.16-1982, " Emergency Planning for Research Reactors.a2 This Standard identifies the elements of an emergency plan which describes the approach to coping with emergencies and minimizing the consequences of accidents at research and test reactor facilities. The emergency plan shall be implemented by emergency procedures.
\\
3American National Standard for Emergency Planning for Research Reactors, ANSI /ANS-15.16-1982, American Nuclear Society, La Grange Park, IL.
I
i This Standard Review Plan (SRP) has been prepared for performing reviews and evaluations for the acceptability of research and test reactor e
radiological emergency plans.
The purpose of the SRP is to assure that uniform evaluations and complete reviews are made of each research or test reactor radiological emergency plan.
The report is organized under ten planning standards which correspond to the guidance criteria in ANSI /ANS-15.16-1982.2 Within the research and test reactor community, the licensed thermal power levels range from 0.1 W to 50 Md.8 The inventory of radionuclides generated in reactor operations and the potential for accidents that, result in a degraded core are largely dependent upon power level and operating history. Hence, the applicability of the planning standards to research and test reactors is also based upon power levels.
Four ranges of power levels (equal to or less than 100 W, greater than 100 W to less than 100 KW, equal to or greater than 100 kW to eqml to or less than 2 Md, and greater than 2 Md) are used in the text.
The applicability of the items under each planning standard to reactors in each range is identified by an "X" in the appropriate column of the review sections.
It should be noted that the radiation dose levels of the emergency 4
action levels established for the various emergency classes in Appendix I are slightly different from those specified for power reactors.
However, in the judgment of the NRC staff, the radiation dose levels specified are adequate for the credible accidents associated with the operation of research and test reactors, and the specified action levels provide reasonable assurance that appropriate measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to develeping emergency action levels that relate directly to facility parameters, e.g., pool water levels and area radiation monitors.
Four standard emergency classes are defined in 10 CFR 50 Appendix E.
The classes are Notification of Unusual Events, Alert, Site Area Emergency, and General Emergency.
The General Emergency class of accidents is not credible for most research or test reactors as.this class is reserved for accidents which could have a significant radiological impact at substantial distances from the reactor. Therefore, most research or test reactors would not include this class as part of their emergency plan.
Acceptable sizes for Emergency Planning Zones (EPZs) are given in Appendix II as a function of authorized steady-state thermal power level.
These are consistent with those given in ANSI /ANS-15.16-1982.
The EPZ size will be determined on a case-by-case basis for any research or test reactors with power levels greater than 50 Md.
aThe planning standards are extracted from American National Standard ANSI /
ANS-15.16-1982, with permission of the publisher, the American Nuclear Society.
3 Power level in this document means authorized steady state thermal power level of the reactor.
2
- 7..
j l
\\
l-CONTENT OF EMERGENCY PLAN An emergency plan shall be prepared that addresses the necessary provi-sions for coping with radiological emergencies.
Activation of tha emergency plan or portions thereof shall be in.esponse to the emergency action levels. In addition to addressing those severe emergencies that will fall I
within one of the standard emergency classes, the plan also shall discuss the necessary provisions to deal with radiological emergencies of lesser severity that can occur within the operations boundary.
The emergency plan should allow for emergency personnel to deviate from actions described in the plan for unusual or unanticipated conditions.
The plan shall consist of the following elements and address, as applicable, the provisions identified for each element.
1 l
e e
0 l
I 3
i
t l
AREA!. OF REVIEW, PLANNING STANDARDS, AND EVALUATION ITEMS 1,0 IKTRODUCTION PLANNING STANDARD The plan should briefly introduce the type of reactor, the reactor's purpose, where it is located, ahd the purposes of the emergency plan. The purpose of the introduction is to provide a general orientation and common understanding about the reactor and the objective of the plan for those members of the reactor organization, the public, and local and federal agencies that will read and study the plan.
Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items 5100 W
<100 kW to 52 MW
>2 MW 1.
The emergency plan should ig include the following:
I a.
A description of the reactor including authorized power level.
X X
X X
b.
A description of the t
location of the reactor facility including access routes. -
X X
X X
c.
Identification of the cwner/ operator.
X X
X X
d.
A definition of the objective of the emergency plan.
X X
X X
.l l
l k
5 i
2.0 DEFINITIONS PLANNING STANDARD Terms unique to the reactor facility or that have a special meaning when used in the plan should be defined in the plan.
I Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items g100 W
<100 kW to 52 MW
>2 MW 1.
The emergency plan should include definitions of words or phrases with meanings specific or unique to the plan or reactor.
X X
X X
w O
6
3.0 ORGANIZATION AND RESPONSIBILITIES PLANNING STANDARD The plan should describe tne emergency crganization that would be activated to cope with radiological emergencies.
This includes the onsite emergency organization and any augmentation from offsite groups.
Persons or groups that will fill positions in the emergency organization should be identified by their normal everyday title.
This organizational description should include as appropriate the following evaluation items.
Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items
$100 W
<100 kW to $2 Md
>2 H4 1.
The emergency plan should describe the following organi-zational considerations:4 a.
The functions as appli-cable to emergency planning of Federal, State, and local government agencies and the i
assistance that they would pro-N vide in the event of an emer-gency.
X X
b.
The reactor's emergency organization, including augmentation of the reactor staff to provide assistance for coping with the emergen,cy situation, recovery from the emergency, and maintaining emergency preparedness.
X X
X X
c.
The arrangements ind agreements, confirmed in writing with local support organizations that would augment and extend the capability of the facility's emergency organization.
X X
X X
l l
l,
'One or more of these positions may be assigned to the same incumbent.
l 7
i
]
Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items 5100 W
<100 kW to 52 Md
>2 MJ d.
A block diagram that illustrates the interrelation-ship of the facility emergency organization to the total emergency response effort.
Interfaces between reactor and other onsite emergency organiza-tion groups and offsite local support organizations and agencies should be specified.
X X
X X
e.
The capability of the emergency organization to i
function around-the-clock for a protracted period of time following the initiation of emergencies that have or could have radiological consequences requiring around the clock emergency response.
X f.
The identification by title of the individual in charge of directing emergency operations, including a line of succession, and responsibilities and au-thorities and those responsi-bilities which may not be delegated (such as notification and protective action decisions). X X
X X
g.
The identification by.
title of the individual, i'ncluding a line of succession, and author-i ity and responsibilities for co-ordinating emer ness planning, gency prepared-updating emergency i
plans and procedures, and co-ordinating plans with other applicable organizations.
X X
X X
4 h.
The identification by title of the individual, with a line of succession, responsible for relating information about the emergency situation to the news media and the public.
X X
8
. =_
1 Applicability by Reactor Operating Power Levels
>100 W to it100 kW i
Evaluation Items
$100 W
<100 kW to 52 MW
> 2 Mn'
- i. The identification by title of the individual, with a line of succession, in charge of radiological assessments l
including his/her responsibi-lities and authority for onsite and offsite dose assessments and recommended protective actions.
X X
- j. The identification by title of the individual, who may authorize reentry into the reactor building or portions of the facility that may have been evacuated during the emergency.
X X
X X
k.
The identification by title of the individual authorized to terminate an h
emergency and initiate recovery i
actions and be responsible for informing the emergency organi-zation of planned organizational actions or changes.
X X
X X
1.
The identification by title of the individual, who say authorize volunteer ernergency workers to incur radiation i
exposures in excess of normal l
occupational limits.
X X
X e
9
i 4.0 EMERGENCY CLASSIFICATION SYSTEM PLANNING STANDARD The emergency plan should describe several classes of emergency situa-tions covering the spectrum of emergency conditions that involve the alerting or activating of progressively larger segments of the emergency organization.
To provide for improved communications between the licensee, Federal, State and local agencies and organizations, the most severe accidents are stan-dardized in four classes of emergency conditions which group the accidents l
according to severity of offsite radiological consequences.
Each emergency i
plan should include only those standard classes eppropriat a for dealing with 3
accident consequences determined to be credible for the specific facility.
Most research reactors have potential emergency situations which may occur (e.g., personnel injury with contamination, fire, etc.) that have less severe offsite consequences than the least severe standard class, "Notifica-tion of Unusual Events." For some research reactors, no credible accidents are postulated which result in consequence matching the least severe class.
However, planning for onsite emergencies is important.
Preparedness for the onsite emergencies should be accomplished by identifying them and including in the plan those elements of this standard commensurate with the postulated emergency situations.
Each class of emergency should be associated with particular emergency action levels and with particular immediate actions to provide appropriate graded response.
In order of increasing severity, the four standard emer-gency classes are described in qualitative terms in the following sub-sections:
4.1 NOTIFICATION OF UNUSUAL EVENTS.
Notification of unusal events may be initiated by either man-made events or natural phenomena that can be recognized as creating a significant hazard potential that was previously nonexistent.
There is usually time available to take precautionary and corrective steps to prevent the escalation of the accident or to mitigate the consequences should it occur.
No releases of radioactive material requiring offsite responses are expected.
One or more elements _of the emergency organization are likely to be activated or notified to increase the state of readiness as warranted by 9.he circumstances.
Although the situation may not have caused damage to the reactor, it may warrant an immediate shutdown of the reactor or interruption of non-essential routine functions.
Situations that may lead to this class include:
(1) threats to or l
breaches of security, such as bomb threats or civil disturbances directed r
toward the reactor; (2) natural phenomena, such as tornados in the immediate e
vicinity of the reactor, hurricanes, or earthquakes felt in the facility; (3) facility emergencies, such as prolonged fires, fuel damage indicated by high coolant fission product activity, or high offgas activity.
0 10
1 I
4.2 ALERT.
Events leading to an alert would be of such radiological significance as to require notification of the emergency organization and its response as appropriate for the specific emergency situation.
Under i
this class it is unlikely that offsite response or monitoring would be necessary.
Substantial modification of rear *or operating status is a higt,ily probable corrective action.
Protective evacuations or isolation of certain areas within the operations boundary or within the site boundary may be neces sary.
Situations that may lead to this class include:
(1) severe failure of fuel cladding or of fueled experiments where containment boun-daries exist to reduce releases or less severe cladding failures in situa-t tions where fission products are not well contained, or (2) significant releases of radioactive materials as a result of experiment failures.
4.3 SITE AREA EMERGENCY.
A site area emergency may be initiated when events such as major damage of fuel or cladding and actual or imminent failure of other physical barriers containing fission products in reactor fuel or fueled experiments have occurred and projected offsite radiological j
consequences exceed Appendix I action levels.
Monitoring at the site l
boundary should be conducted to assess the need for offsite protective actions.
Protective measures on site may be necessary.
4.4 GENERAL EMERGENCY.
A ceneral emergency may be initiated by accidents which result in an uncontrolled release of radioactive material into the air, water, or ground to the extent that protective actions offsite may be necessary. This class of accident is not credible for most research g
reactors.
Therefore, most research reactors would not include this class as i
y part of their emergency plans.
A protective action that may be recommended to offsite authorities may be to shelter the general public within the EPZ.
State and local government response organizations have the ultimate responsibility for initiating and implementing any recommended offsite protective actions.
Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items 5100 W
<100 kW to 52 K4
>2 HW 1.
The emergency plan.should
\\
contain:
a.
An emergency classification system consistent with the planning standard.
X X
X X
b.
In an Appendix to the plan, a listing by title of imple-menting procedures for each class of emergency.
X X
X X
i l
11 i
\\
\\
T
~
~
~
6.
M JA-i I
5.0 EMERGENCY ACTION LEVELS PLANNING STANDARD Because of the wide diversity in research reactors (power level, engineered safety features, site environment, etc.), those conditions which might initiate or signal a radiological incident having particular offsite consequences will vary widely among facilities.
Action levels may be specified for effluent monitors or other plant parameters for which the dose rates and radiological effluent releases at the site boundary can be pro-jected. To establish effluent action levels, facilities that have meteoro-logical information available may base the action levels on' actual meteoro-logical conditions; otherwise, the criteria for downwind concentration, Section 4 of ANSI /ANS 15.7-1977, "Research Reactor Site Evaluation," should be used.
Each emergency plan should establish emergency action levels appropriate for the specific facility and consistent with Appendix I.
The emergency plan should include emergency action levels to initiate protective actions for members of the general public onsite.
The protective action guide (PAG) shall be 1 rem whole body or 5 rem thyroidd Applicability by Reactor.
Operatina Power Levels i
>100 W to it100 kW Evaluation Items
$100 W
<100 kW to 52 Kd
>2 M4 1.
Each licensee's emergency plan should contain:
a.
Emergency action levels which are appropriate to the specific facility and consistent with Appendix I.
To the extent possible specify effluent monitors used to project dose rates and radiological effluent releases at the site boundary.
X X
X X
i 3Manual of protective Action Guides and Protective Actions for Nuclear Incidents, EPA-520/1-75001, Sept. 1975, U.S. Environmental Protection Agency.
0 12
i I
I l
- 6. 0 EMERGENCY PLANNING ZONES lI%
l PLANNING STANDARD As part of emergency planning, the reactor owner / operator of a facilit that identifies radiological emergencies which result in offsite plume ex y l
posures exceeding 1 rem whole body or 5 rem thyroid should identify an emergency planning zone (EPZ).
The postulated radioactive release from credible accidents provides the basis for determining the need for an EPZ.
The size of the EPZ should be established so that the dose to individuals l
beyond the EPZ is not projected to exceed the PAG.
As an alternative to performing such calculations, the EPZ sizes in Appendix II may be adopted i
according to the power level.
Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items 1100 W
<100 kW to 52 M4
>2 HW 1.
Ensure that the emergency plan identifies the EPZ.
X X
X X
r 2.
If the EPZ is not consistent with Appendix II, the plan chall include an acceptable basis for the EPZ.
X X
X X
l \\.
t e
i i
e l(
l 13
7.0 EMERGENCY RESPONSE PLANNING STN!DARO l
Emergency response measures should be identified for each emergency.
These response measures should be related to the emergency class and action levels that specify what measures are to be implemented.
Applicability by Reactor Operating Power Levels
>100 W to 1100 kW Evaluation Items
$100 W
<100 kW to 52 M4
>2 M4
~
1.
The emergency plan should cover the following notification information for emergency response:
a.
The actions to notify and mobilize the emergency organi-zation and the applicable offsite support organizations for each emergency class.
X X
X X
b.
The location (s) of current A
notification lists.
X X
X X
y c.
Describe the contents of initial and followup emergency messages to the NRC and, when applicable, to offsite authori-ties. To the extent known, these messages should include the following:
(1) Name, title and tele-phone number of caller, a6d the location of the incident and the emergency class.
X X
i
~
(2) Description of emergency event.
X X
(3) Date and time of incident initiation.
X X
(4) The type and quantity of radionuclides released or expected to be released.
X X
04 14 l
.a l
l Applicability by Reactor
}
Operating Power Levels l
r
>100 W to 2100 kW Evaluation Items 5100 W
<100 kW to 52 MW
>2 MW (5) Impact of releases and recommended offsite emergency actions.
X d.
A method is established to insure that offsite authorities have received the initial message and that it is authentic.
X X
2.
The emergency plan should cover the following assessment considerations:
a.
A description of methods for gathering and processing information for essessment actions.
X X
3.
The emergency plan should provide a summary description of those actions that could be j
taken to mitigate or correct the problem for each emergency class.
X X
X X
4.
The emergency plan should describe protective actions appropriate for the emergency class. The emergency plan should include the foMowing:
a.
Conditions for either partial or complete onsite evacuation, evacuation routes, and primary and alternate assembly areas.
X X
X X
b.
Methods to" ensure per-sonnel accountability and the segregation of potentially con-i taminated personnel.
X X
X X
c.
Protective measures and exposure guidelines for emer-gency personnel.
X X
X X
15 4
- - - - - + =
w
,- -, - = -
g,-,
er r py 3
=
,&e
-.w,-
ee---m,
.-ray--
u Applicability by Reactor Operating Power Levels S
>100 W to 2100 kW Evaluation Items
$100 W
<100 kW to 52 MW
>2 MW d.
Provisions for isolation l
and access control of facility areas to minimize exposures to radiation and the spread of radioactive contamination.
X X
X X
e.
The methods for monitor-ing radiation dose rates and con-tamination levels, both onsite and offsite, including provisions for transmitting collected in-formation and dcta to the ele-ment of the emergency organiza-tion responsible for accident X
X assessment.
X X
O O
1 16 i
i
~:
i i
i l
i i
8.0 EMERG[NCYFACILITIESANDEQUIPMENT l
/
PLANNING STANDARD The emergency plan should briefly describe the emergency facilities, types of equipment and their location.
Applicability by Reactor Operating Power Levels
>100 W to 2100 kW i
Evaluation Items 5100 W
<100 kW to52yd
>2 MW 1.
The emergency plan should describe an emergency support i
i l
center (ESC).
X 1
X X
(
l 2.
Representative types of l
monitoring and sampling equip-
{
ment to be used for accident assessment and their location.
These should include:
a.
Portable and fixeo radio-logical monitors.
X X
X X
t b.
Sampling equipment.
X X
X X
s c.
Instrumentation for spec-ific radionuclide identification and analysis.
X X
X, X
t d.
Personnel monitoring equipment.
X X
X X
e.
The plan should also de-scribe nonradiological monitors or indicators that may pre. vide pertinent information;.for example:
(1) Reactor *instru-mentation.
X (2) Fire detectors, earthquake sensors, etc.
X X
X X
(3) Source of meteoro-logical data representative of facility location.
X 17
Applicability by Reactor Operatino Power Levels
>100 W to 2100 kW Evaluatior. Items 5100 W
<100 kW to 52 MW
>2 MW 3.
The emergency plan should identify those rteasures that aill be used to provide necessary assistance to persons injured or exposed to radiation. The capabi-lities for decontamination, admin-istering first aid, transporting injuredpersonnel,andarrange-ments for medical treatment should be described. The following items should be included:
a.
Facilities for personnel decontamination.
X X
X X
b.
Methods for handling and transport.ingcontaminatedinjured personnel.
X*
X X
X c.
Written agreements with hospitals to ensure that medical services are available and the staff is prepared to handle radiological emergencies.
X X
X X
4.
The emergency plan should adequately identify the emergency communications systems that will be available to communicate instructions and information both onsite and offsite through-out the course of an emergency.
X X
X X
~
5.
Fa:ilities planning for a site area emergency should esthblish reliable means cf communication, e.g., public telephone ar.d radio, that is compatible with local off-site support groups.
X O
18
.r
^^
^
\\
i I
1
] }
9.0 RECOVERY l
PLANNING STANDARD j
i This element of the emergency plan should describe the criteria for 1
i restoring the reactor facility to a safe status including reentry into the reacter building or portions of the facility that may have been evacuated i
because of the accident.
The operations to recover from most severe accidents will be complex and depend on the actual conditions at the facility.
It is not i
practicable to plan detailed recovery actions for all conceivable situations.
l 1
Applicability by Reactor i
Operating Power Levels l
>100 W to 2100 kW Evaluation Items
$100 W
<100 kW to 52 W
>2 W 1.
The emergency plan should l
specify a.
That recovery procedure (s) will be written and approved as i
needed.
X X
X X
a i
l i
l
~
1 i
\\
3 19 i
l l
l 10.0 MAINTAINING EMERGENCY PREPARE 0 NESS r
PLANNING STANDARD The emergeno pian should describe the elements necessary for r.aintaining an acceptable state of emergency preparedness.
A description should be pro-vided of how the effectiveness of the emergency plan will be maintained, including training, review and update of the emergency plan and associated implementing procedures, and maintenance and inventory of equipment and suppliet that would be used in emergencies.
Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items 5100 W
<100 kW to 52 Rd
>2 MW 1.
The emergency plan should describe an initial training and periodic retraining program designed to maintain the ability of emergency response personnel to perform assigned functions for the following:
a.
Personnel responsible for decisionmaking and transmitting emergency information and instruc-tions.
X X
X X
b.
Personnel responsible for accident assessment.
X X
X X
c.
Radiological monitoring and analysis teams.
X X
X X
d.
First aid and rescue
~
personnel.
X X
X X
~
e.
Medical support personnel X X
X X
f.
Police, security, ambu-lance and fire fignting personnel.
X X
X X
2.
The emergency plan should provide for:
O 20
i.
i
~
l I
Applicability by Reactor h
Goerating Power Levels
>100 W to 2100 kW Evaluation Items
$100 W
<100 kW to 52 MW
>2 MW a.
Annual onsite emergency drills, to be conducted as action drills.6 X
X X
X b.
Provision for critiques of all drills, including timely eval-uation of observer comments and correction of identified deficien-cies.
X X
X X
c.
Development of written scenarios for conducting annual i
action drills.
X X
X X
i I
l 3.
The emergency plan should provide for a biennial review i
and update of the emergency plan and implementing procedures i
l and agreements with offsite i
support organizations and agencies i
j including:
a.
Reviews and approvals by those responsible for emergency planning.
X X
X X
b.
Incorporation of modifi-cations resulting from action drills or changes in the facility or envirore.
X X
X X
c.
Timely forwarding of l'
approved amendments to the plan, agreements, and implementing j
procedures to authorized individuals, agencies and support organizations.
X X
X X
- An action drill tests the integrated capability of the emergency plan, or a component thereof, and may include instruction periods to develop and maintain skills in a particular operation.
21
1 Applicability by Reactor Operating Power Levels
>100 W to 2100 kW Evaluation Items
$100 W
<100 kW to 52 MW
>2 MW 4.
The emergency plan should describe the provisions to ensure operational readiness of emergency communications and emergency health physics equipment by including:
a.
Required maintenance and minimum calibration frequency.
X X
X X
b.
Functional testing inclu-ding minimum frequency.
X X
X X
c.
Minimum frequency of, inventory for equipment and supplies.
X X
X X
0 b
l i
l 22 i
i
APPENDIX !
EMERGENCY CLASSES l
Emergency Class Action Leve18 Purpose i
i Notification of Actual or projected radiological (2) Ensure that the first Unusual Events effluents at the site boundary step in any response later exceeding 10 MPC2 when averaged found to be necessary has over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 15 arem whole been carried out. (2) bring body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
the operating staff to a state of readiness, and Report er observation of severe (3) provide systematic natural phenomenon.
handling of unusual events information and decision-Receipt of bomb threat.
making.
Alert Actual or projected radiological (1) Ensure that emergency
't effluents at the site boundary personnel are readily exceeding 50 MPC2 when averaged available to respond if over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 75 mrem whole the situation becomes more body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, serious or to perform confirmatory radiation Actual or projected radiation monitoring if required, levels at the site boundary of and (2) provide current 20 mrem /hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whole body offsite authorities or 100 mrem thyroid dose.
status information.
Site Area Actual ; projected radiological (2) Ensure that response k
Emergency effluents at site boundary exceed-centers are manned, (2) i y
ing 250 MPC8 when averaged over i
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 375 arem whole ensure that monitoring
[
body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
teams are dispatched, (3) ensure that personnel i
l Actual or projected radiation required for evacuation of j
1evels at the site boundary of onsite areas are at duty stations, (4) provide con-i 100 arem/hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whole sultation with offsite l
body or 500 mree thyroid dose.
authorities and (5) provide infor*ation for he public
~
through offsite authorities.
General Emergency Sustained actual or projected (1) Initiate predetermined l
radiation levels at the site protective actions for boundary or 500 mrem /hr whole the public, (2) provide j
- body, continuous assessment of Actual or projected dose at the information from licensee I
site boundary in the plume and offsite organization measurements. (3) initiate exposure pathway of 1 rem whole additional measures as j
body or 5 rem thyroid.
Indicated by actual or I
potential releases, (4) i provide consultation with offsite authorities, and (5) provide updates for the j
public through offsite authorities.
'The situations tnat may lea 1 to an emergency class cescribed in the subsections of Section 4.0 may be referenced as emergency actions levels appropriate to the emergency class.
2 Maximum Permissible Concentration (MPC) as listed in Title 20, of the Code of l
k Federal Regulations Part 20. " Standards for Protection Against Radiation,"
j i
)
7 Appendix B, Table !! Column 1.
23 l
l
6---'44 44---
Ah-*-
-4J A4-We4 a
e-
a4 Z-t-dwi M
,u no 2.4.--a-
.- M b-4
-4a4-4mm
+-D4--&'-
4A 4-4--
m--EL-um_
--eA- - -
--3L4 5
a e
i
)
i i
L J
i 1
4 i
i i
i 1
s 5
4 4
)
i I
i f
i 4
5 4
)i o
i i
1
,I 5
l
-ll -
- s
+
y
' h i
i i
i i
J i
i i
4 h
i 4
I i
.i
.I l
9 a
ii -
4 4
I l
8 t
e n
}
d 4
4 d
4 i
n 1
]
1
.i I
.1 1
i 5
f i
o i
9
)
q.-
+ --
---,-mm.,-----
--,..-c
.---w=r.-w-
=v e.
- =
,w,-*,.vw-.-rr, e-.,,,--.+...-e,,.,
v-e.wwe.-,-Er 1,,, -.
.wsr o m
.w.-r,-(
g
.o 1
1 i
APPENDIX II Alternate Method For Determining j
The Size of an EMERGENCY PLANNING 20NE1 Authorized Power Level Acceptable EPZ Size 52 Md Operations boundary I
>2 Md and 110 MW 100 meters i
i
>10 Md and $20 M4 400 meters i
2
>20 Md and 150 MW 800 Meter.s a
>50 Md Will be determined on a case-by-case 4
basis r
l i
i l
i i
' Calculations are based on:
D. Bruce Turner, Work Book of Atmospheric Dispension Estimates, Office of t
Air Programs.
U.S. Environmental Protection Agency, Washington, D.C.
(1970)
D. H. Slade, Ed.,
- Meteorology and Atomic Energy." U.S. Atomic Energy Commission, Washington, D.C. (1968); and WASH 1400 (NUREG 75/014), " Reactor Safety Study," Appendix VI. U.S. Nuclear Regulatory Commission, Washington, D.C. (1975).
6 4
25
- ~
- - - - - ~ --
-- l
l Revision 1
/#*%
U.S. NUCLEAR REGULATORY COMMISSION March isas j
4
)
) OFFICE OF NUCLEAR REGU GUIDE
@o*
o...+
i l
REGULATORY GUIDE 2.6 i
(Task HF 2014)
EMERGENCY PLANNING FOR RESEARCH AND TEST REACTORS 1
A. INTRODUCTION threaten to cause radiological hazards affecting the health and safety of the public. Emergency plans should be Paragraph 5034(b)(6)(v) of 10 CFR Part 50," Domestic directed toward rnitigating the consequences of emergencies licensing of Production and Utihzation Facilities," requires and should provide reasonable assurance that appropriate that each application for a license to operate a facility measures can and will be taken to protect the health and include in a Final Safety Analysis Report (FSAR), along safety of the public in the event of an emergency. Although j
with other information, the applicant's plans for coping it is not practicable to develop a completely detailed plan with emergencies, including the items specified in encompassing every conceivable type of emergency Appendix E, " Emergency Plannmg and Preparedness for situation, advance planning and provisions for ensuring the Production and Utihzation Facilities," to 10 CFR Part 50.
availability of necessary equipment, supplies, and services i
Paragraph 50.54(q) reauires bcensees to follow and can create a high order of preparedness and ensure an l
maintain in effect emergency plans that meet the require-orderly and timely decisionmaking process at the time of an ments of Appendix E to 10 CFR Part 50.
emergency.The plans should be an expression of the overall concept of operation that describes how the elements of his regulatory guide proddes licensees and applicants advance planning have been considered and the provisions l
with a method acceptable to the NRC staff for complying that have been made to cope with emergency situations.
l with the Commission's regulations with regard to the content of emergency plans for research and test reactors.
In the judgment of the NRC staff, the potential radio-logical hazards to the public associated with the operation i
Any guidance in.his document related to informa-of research and test reactors arc considerably less than tion collection activities has been cleared under OMB those involved with nuclear power plants. In addition, Clearance No. 3150-0011.
because there are many different kinds of research and test reactors, the potential for emergency situations arising and B. DISCUSSION the consequences thereof vary from facility to facility.
These differences and variations are expected to be reflected Working Group ANS-15.16 of the American Nuclear realisticaDy in the emergency plans and procedures developed
{
Society Subcommittee ANS15 has developed ANSI /
for each research and test reactor facility.
ANS 15.16-1982, " Emergency Planning for Research i
Reactors,"' which is generally consistent with current C. REGULATORY POSITION l
regulatory requirements. This standard was developed to provide specific acceptance criteria for complying with the ne requirementsin ANSI /ANS 15.16-1982," Emergency applicable requirements set forth in f 50.54 andin Appen-Planning for Research Reactors," are generally acceptable da E to 10 CFR Part 50. These criteria provide a basis for to the NRC staff as a means for complying with the require-research and test reactorlicensees and applicants to develop ments in f 50.54 and in Appendix E. " Emergency Planning acceptable radiological emergency response plans and and Preparedness for Production and Utilization Facilities "
improve emergency preparedness at their facilities, to 10 CFR Part 50 as related to research and test reactors, subject to the fo!!owing clartfications.
The Commission's interest in emergency planning is focused primanly on situations that may cause or may
- 1. Responsibility for planning and implementing all
= copies may be obtained from the American Nuclear society, emergency meam u W site bodaries rests M sss North Kensington Avenue,Le Grange Park, til 60s2s.
the licensee. In this context, the site boundaries should be l
USNRC REGULATORY CUIDE$
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission. Washington, D.C. a0sss.
Rrgulatory Culdes are issued to oescribe one make available to the Attention: Docketeng anc serv 6ce Branch.
pu blic enethwis acceptable to the NRC staff of imp 6ement6ng specific parts of the Commission's regulat6ons. to ceI6neste tech-Tne pulpes are issued in the following ten broad OMslons:
n6 sues usea py the staff in evaluating specific problems of postu-hoc acc6 cents or to prov60e gu6cance to appl 6 cants. Repuistory
- s. Power Reactors
- 6. Proeucts Gusces are nol substitutes f or reputations. and compliance with
- 2. Research and Test Raattors
- r. Transportetton them es not tenuires. Methocs ane solut6ons estferent from those set
- a. Fuels and Matersa:s Factitt6es
- a. Occupat6onas Health out in the guepes will be acceptable af they prow.oe a basis for the
- 4. Env6eonenentet anc sitmp
- 9. Antitrust and Financlaf Review tmoengs reouestte to the tasvance or continuance of a permit or
- 5. Maternals enc Ptant pvotection so. Generat tacense by the Comm6sshon.
Copies of assued pulpes may be purchase 6 at the current Government This pulos was lasued after consleeration of comments received from Pr6nt6ng Off ce pr6ce. A subscript 6on so v6ce for future pu6ees in spe-i the publ6c. Comments and suppestions for 6mprovements en these cifec devisions ns avaltable through the Government pr6nting Of t cs, i
punoes are encourages at att temos, anc pueces wilt be revisen, as enformation on the subscription serv 6ce anc current GPo prices may s poropriate. to accommoeate comments anc to ref6ect new enforme.
be obta6ned by writing the U.S. Nuclear Reputatory Comm6ssion.
tun or esper6ence.
Washington, D.C. 20sss, Attention: Publ6 cations Sales Manager.
w
c!carly defined. Supporting organizations that would and step by step procedures or checkhsts that may be augment the licensee's emergency organization, e.g., fire altered as a result of experience or test exercises, should not department, hospitals, and security organizations, should be be incorporated into the plans but should be listed in the specified. Planning and implementation of measures to cope emergency implementing procedures.
E with reactor-related emergencies beyond the site boundary should be commensurate with and based on the potential
- 5. Emergency procedures that implement the emergency consequences of credible accidents or incidents. The plan need not be incorporated into the plan but should be emergency plan should describe this planning basis and the listed by title in an annex to the emergency plan. The corresponding arrangements and agreements among the emergency implementing procedures should be maintained licensee and the local, State, or Federal agencies expected and available at the facility for inspection and review at any to respond.
time by a representative of the NRC.
- 2. The radiation dose levels of the emergency action levels established for the various emergency classes are
- 6. The procedural system used by the licensee for the shghtly different from those specified for power reactors.
review and approval of emergency implementing procedures However,in the judgment of the NRC staff, the radiation should contain instructions governing the mTiting, revising, dose levels specified in Table I of the standard are adequate and updating of implementing procedures. The instructions for the credible accidents associated with the operation of should specify the methods to be used to ensure that research and test reactors, and the specified action levels procedures, revisions,and changes are reviewed for adequacy, provide reasonable assurance that protective measures approved for use, and distributed to user organizations and associated with the action levels specified in Table I can and individuals having the responsibility for implementing the mill be taken, prouded appropriate emphasis is also given to procedures.
developing emergency action levels that relate directly to facihty parameters (e.g., pool water levels and area D. IMPLEMENTATION radiation monitors).
Except in those cases in which an applicant or licensee
- 3. Emergency action levels related to facility parameters, proposes acceptable alternative practices or methods for effluent release levels, and equipment conditions should be complying with specified portions of the Commission's developed to the extent feanble for each emergency class.
regulations, the practices or methods described in this guide will be used as a basis for evaluating,the adequacy of the
- 4. Details that can reasonably be expected to change emergency plans and preparedness of applicants for a from tune to time, e.g., names and telephone numbers, license to operate a research or test reactor as well as the specific items of equipment and supplies, inventory lists, plans and preparedness of current licensees for such reactors.
O A
2.6-2
1 i
i VALUE/ IMPACT STATEfAENT
- 1. THE PROPOSED ACTION
- 2. TECHNICAL ALTE,RNATIVES l
The licensee of a research and test reactoris required by Because the replatory guide would endorse a consensus i
the Commission's regulations to develop plans for coping standard, no technical alternatives have been considered.
sith emergencies. Specific guidance is needed to provide acceptance enteria for complying with the applicable require-
- 3. PROCEDURAL ALTERNATIVES ments set forth in { 50.54 and in Appendix E of 10 CFR I
Part 50. Regulatory Guide 2.6, " Emergency Planning for Because ANSI /ANSs 15.16-1982 is generally consistent Research and Test Reactors," provides basic guidance for with current regulato'ry requirements, revising Regulatory complying with the regulations. More definitive guidance, Guide 2.6 to endorse that standard was selected as the howeser, has been developed by the American Nuclear appropriate procedural alternative.
Society Subcommittee ANS-15 in ANSI /ANS 15.16-1982, d
'r i
- Emergency Planning for Research Reactors." The proposed
- 4. STATUTORY CONSIDERATIONS action would endorse this standard with appropriate supple-3 mentary materialin a revision to Regulatory Guide 2.6.
4.1 NRC Authority j
1 1.1 Valuellmpact Assessment Authority for this action is derived from the Atomic Energy Act of 1954, as amended, through the Commission's j
The proposed action would provide licensees and appli-regulations in Title 102.Ebepter I, of the Code of Federal cants definitive pidance for developing emergency plans Regulations.
8 hat meet the apprornate regulation.
4.2 Need for NEPA Agasment,.,,.
I'ah<c -De value of the proposed action would be more effective emergency preparedness around research and test Since the guidance in the proposed replatory guide reactors. Endoning a national consensus standard reduces the revision does not represent a major action as defined by expenditure of staff resources in developing the guidance.
paragraph S t.5(a)(10) of 10 CFR Part S t implementation of the regulatory guide does not require a NEPA assessment.
1 Impact - Most of the impact on industry has already occurred dunng development, review, and approval of the i
consensus standard and in attempting to comply with the
- 5. RELAT10NSHIP TO OTHER EXISTING OR PROPOSED j
upgraded emergency preparedness requirements promul-REGULATIONS OR POLICY gated in August of 1980. For those members of the research reactor community that have not previously This revision to Replatory Guide 2.6 relates to the NRC upgraded their emergency plans,it is estimated that it will emergency preparedness regulations, Regulatory Guide 1.101, take approximately 2 man-months to do so.
1.2 Decision on the Action
- 6.
SUMMARY
AND CONCLUSION Replatory Guide 2.6 should be revised to endorse ANSI /ANS 15.16-1982.
A revision to Regulatory Guide 2.6 should be published.
i a
I
~
l 2.63
ENNgC 416 A EMERGENCY PLAN t
i for the UNIVERSITY OF ARIZONA RESEARCH REACTOR i
5 Facility License R-52 l
' i Docket 50-113 l
t I
l 1
)
i Revision 2 January 30,1990 e
e a
(
)
1 4
4-4 i
1 4
1 TABLE OF CONTENTS l
4 l
i i
1 Page 1
1.0 Introd u ction............................................. l 1.1 Application
.........................................I 12 Objective........................................... !
1.3 Site Description...................................... 1 1.4 Reactor Facility Description.............................. 2 i
1.5 Reactor Utilization and Operating Frequency................... 3 l
i i
1 2.0 De finitions............................................. 3 3.0 Organization and Responsibilities............................... 5 3.1 Emergency Organization................................5 3.1.1 Emergency Director.............................. 6 3.1.2 Emergency Coordinator............................ 7 3.1.3 R eactor Operator................................ 7 3.1.4 NRL Mana g ement............................... 7 i
3.1.5 Univenity Office of Public Information................. 7 3.1.6 Radiation Control Office........................... 7 l
3.1.7 Department Personnel............................. 8 3.1.g Unive rsity Police................................. 8 i
3.1.9 Police Dispatcher................................ 8 j
1 3.1.10 Fire Emergency Services......... '.................. 9 l
j.
3.1.!! University Hospital
..............................9 3.1.12 Off-Site Law Enforcement Agencies
...................9 3.2 Coordination with and Notification of Other Agencies............
10 -
1 3.2.1 U.S. Nuclear Regulatory Commission -..................
10
{
3.2.2 Arizona Radiation Regulatory Ageney
.................10 1
3.2.3 Local Government Agencies........................
10 3.2.4 University Department of Risk Management and Safet Termination of an Emergency.....................y....... I1 3.3 3.4 Authorization for Reentry..............................
11 3.5 Authorization of Radiadon Exposures in Excess of 10CFR20 Limits...
11 4.0 Emergency Classification System..............................
12 4.1 Non-Reactor Safety Related Events -........................
12 '
i 4.2 Notification of Unusual Events...........................
12
^
4.3 Alert.............................................
13 4.4 Site Area Emergency.................................
13 4.5 General Emergency..................................
13 5.0 Emergency Action Levels (EAL's).............................
13 -
6.0 Emergency Planning Zone..................................
14 11
i I
I Table of Contents (continued) j Page j
7.0 Emergency Response
.....................................14 i
7.1 Activation of the NRL Emergency Organization................
14 j
4 7.2 Protective Action Values...............................
14 i
7.3 Radiation Control Office Emergeney Response Program............ 15 7.4 Reporting of Emergencies..............................
15
)
7.5 Emergency Response for Non-Reactor Safety Related Events.......
16 7.5.1 Activation of the Emergency Organization l
for Non-Reactor Safety Related Events.................
16
)
a 7.5.2 Assessment Actions for Non-Reactor Safety Related Events....
16 7.5.3 Corrective Actions for Non-Reactor Safety Related Events....
16 j
7.5.4 Protective Actions for Non-Reactor Safety Related Events....
17 7.6 Emergency Response for Notification of Unusual Events..........
17 7.6.1 Activation of the Emergency Organization for Notification of Unusual Events
...................17 7.6.2 Assessment Actions for Notification of Unusual Events
.......I8 7.6.3 Corrective Actions for Notification of Unusual Events.......
19 l
7.6.4 Protective Actions for Notification of Unusual Events.......
20 0
Emergency Facilities and Equipment
....................,......20 8.1 Emergency Support Center (ESC)
.........................20 8.2 Assessment Facilities..................................
21 8.3 First Aid and Medical Facilities
..........................21 8.4 Decontamination Facilities..............................
21 8.5 Communications Systems...............................
22 9.0 Recovery Operations.....................................
22 I
10.0 Maintaining Emergency Preparedness...........................
22 10.1 Training
.........................................22 I
10.2 Conduct of Drills and Exercises
..........................23 10.3 Critiques of Dri!!s and Exercises..........................
23 10.4 Emergency Plan Review and Update '.......................
23 10.5 Emergency Equipment Maintenance and Surveillance.............
24 10.5.1 Inventory of Emergency Supplies and Equipment..........24 10.5.2 Radiation Monitoring Equipment Cheeks and Calibrations.....
24 III 1
1
?
i i
i i
LIST OF ILLUSTRATIONS Figure Page l
University of Arizona Campus Map..............................
25 2
Section of Nonh Wing of the Engineering Building....................
26 l
3 NRL Emergency Organization ~................................
27 APPENDIX A:
Agreement Letters Radiation Control Office University Hospital City of Tucson Fire Department 4
Korts Ambulance Service University of Arizona Police Department I
h i
[
?
6 All IV y - ---
r e-
,-,.m,,
w-
., -.+cw-ma e-,,w-r.-.----.-
,twwwyi.-r,--,ww
,r y
w, e,wre e-co--.w-i,w'e
+.,
! Approved by the Reactor Committee on October 29,1982 Revision 2, January 30,1990 EMERGENCY PLAN FOR THE UNIVERSITY OF ARIZONA NUCLEAR REACTOR LABORATORY 1.0 Introduction 1.1 Application This emergency plan applies to the Univenity of Arizona Nuclear Reactor t
i_aboratory (NRL). De University of Arizona Research Reactor (UARR), a Mark 1 l
TRIGA reactor, is licensed pursuant to Title 10. Code of Federal Regulations, Chapter 1, Part 50, as. research and utilization reactor, Facility Operating License No. R-52 (Docket No. 50-113).
The University has a campus-wide radiological emergency plan which is I
intended to integrate radiological emergency planning at all campus facilities using l
radioactive materials or radiation producing devices. The NRL Emergency Plan is an integral part of the University of Arizona emergency plan and specifies the objectives and implementing procedures to be followed for emergency situations l
occurring at the NRL.
1.2 Objective The objective of this emergency plan is to provide a basis for action and designate areas of responsibility to cope with an emergency at the NRL that may l
l affect ti e public health and safety. Additionally, the plan identifies the off-site I
support organizations that may be contacted for assistance if required.
1.3 Site Description i
The University of Arizona Nuclear Reactor Laboratory is located on the first floor of the north wing of the Engineering Buiding (Building 20) on the University of Arizona Main Campus. A map of the main campus is attached as Fig.1. The l
l i
i
! of Arizona Main Campus. A map of the main campus is attached as Fig.1. The i
campus is centrally located in the city of Tucson, Arizona, and is bounded roughly l
i by East Speedway Boulevard, North Campbell Avenue, East Sixth Street, and North l
Park Avenue, which are shown in Fig.1.
3 Three adjacent rooms in the Engineering Building are permanently established as the Reactor Laboratory and are designated a controlled access area. These are:
4 Room 122, the Control Room; Room 124, the Reactor Room; and Room 124A, an I
equipment storage and experiment setup room which also houses a natural I
uranium / water suberitical assembly. Figure 2 is a plan of the north wing of the l
building, showing these rooms.
1A Reactor Facility Descriptions The UARR is a TRIG /. Mark I licensed to operste at a maximuin steady-state f
j thermal power of 100 kilowatts rend in the pulse mode with reactivity insertions up to 52.50.
t r
The reactor core is located in a swimming pool type tank which is 21 feet deep i
t and 6.5 feet in diameter, located below grade in Room 124 The tank contains approximately 5000 gallons of demineralized water. The reactor fuel consists of :
standard stainless-steel clad TRIGA fuel elements, instrumented elements, and fuel a
followers for the control rods. The U-235 enrichment of the fuel is less than 20 percent. Irradiated fuel is located either in the' reactor core or in safe geometry storage racks in the reactor pool.
The reactor pool water provides shielding of the samma radiation produced during operation and from the irradiated fuel. During operation, the water is cooled by refrigerstion coils submerged in the pool. A pump, filter, and demineralizer unit are used to maintain water purity. Inlet and outlet pipes extend from the reactor pool to the deminerali:er system. Vent holes have been drilled in the intake 'and outlet pipes approximately two feet below normal pool-water level to assure that any_
i l
! siphoning action woc!d be broken at this level of pool water. This depth of water is i
sufficient to provide shielding for the irradisted fuel.
1.5 Resetor Utilization and Operating Frequency The NRL is a teaching facility of the Department of Nuclear and Energy i
Engineering, and is also used for irradiation services, primarily for activation analysis, for faculty and students in many other departments of the University of Arizona. Less than one percent of operation is done as a service to industrial firms.
Thu the primary operation is for laboratory courses, thesis research and irradiation services. Typical operation in one month may include 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of operation at powers of I kilowatt or less, one or two irradiations of one hour duration at 100 kilowatts and one irradiation of three or four 1ours duration at 100 kilowatts.
Operation of the reactor takes place about three days per week for about three hours I
cach day. The total average energy output is 0.40 Megawatt days per year.
I 2.0 Definitions emergency. A condition which calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.
emergency action levels. Radiological dose rates; specific contamination levels of airborne, waterborne, or surface-deposited concentrations of radioactive materials; or specific i
f instrument readings that may be used as thresholds for initiating specific emergency measures.
emergency plan. A document that provides the basis for actions to cope with an J
emergency. It outlines the objectives to be met by the emergency procedures and defines the authority and responsibilities to achieve such objectives.
emergency planning zone (EPZ).
Area for which offsite emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The EPZ for the NRL consists of the NRL facility itself, consisting of rooms 122,124 and 124A of the Engineering Building.
i I
4 emergency procedures. Emergency procedures document in detail the implementation actions and methods required to a:hieve the objectives of the emergency plan.
he. In this plan, the word 7.e" is used in its generic sense, denoting either male or female person.
NRL. The University of Arizona Nuclear Reactor Laboratory, R._oom 122,124 and 124A of the Engineering Building containing the University of Arizona Research Reactor and
. supporting equipment.,
offsite. The geographical area that is beyond the site boundary and outside of the control of the reactor owner / operator. _In this context, offsite refers to any location other than Room 122,124, and 124A of the Engineering Building.
onsite. The geographical area that is within the site boundary and w:ach is administratively controlled by the reactor owner / operator.
operations boundary. The area where the reactor chief administre. tor has direct authority over all activities. For the NRL, this consists of the NRL facility itself, rooms 122, 124, and 124A of the Engineering Building. his area has prearranged evacuation procedures known to personnel frequenting the area.
protective action guides (PAG). Projected radiological dose or dose commitment values to individuals that warrant protective action following a release of radioactive material.
Protective actions would be warranted provided the reduction in individual dose expected to be achieved by carrying out the protective action is not offset by excessive risks to individual safety in taking the protective action. The projected dose does not include the dose that has unavoidably occurred prior to the assessment.
research reactor. A device designed to support a self-sustaining neutron chain reaction for research, developmental, educational, training, or experimental purposes, and which may have provisions for production of nonfissile radioisotopes.
site boundary. The site boundary is that boundary, not necessarily having restrictive barriers, surrounding the operations boundary wherein the reactor administrstor may
i
- t directly initiate emergency activities. The area within the site boundary may be frequented by people unacquainted with reactor opentions.
shall, should and may. The word "shall" is used to denote a requirement; the word
'should" to denote a recommendation; and the word "may" to denote permission, t
neither a requirement nor a recommendation.
UARR. De University of Arizona Research Reactor, a Mark I TRIGA Reactor.
3.0 Organization and Responsibilities The University of Arizona Reactor is opersted by the University under license from the United States Nuclear Regulatory Commission (NRC). It is a facility of the Department.
f of Nuclear and Energy Engineering, through which it receives primary funding for staff and equipment. The chief administrstor of the Nuclear Reactor Laboratory is the Dir aor of f
i the Nuclear Reactor Laboratory, who is appointed by the President of the University. The i
Director of the Nuclear Reactor Laboratory is responsible in a line of authority tc the Head of the Department of Nuclear and Energy Engineering, who is responsible to the Dean of the College of Engineering. He University of Arizona Reactor Committee reviews reactor operation, and approves changes, experiments, and procedures in accordance with the Technical Specifications and 10CFR50. The Reactor Supervisor is a licensed Senior Operator j
i 1
who as responsible for the day-to-day operation of the facility under the Director of the Nuclear Reactor. Other staff members of the NRL include faculty members who are licensed by the NRC as senior reactor operators (SRO), and students who are licensed by the l
NRC as reactor operstors (RO), and who may operate the reactor with the authorization of a SRO. Through training and operating experience, the staff is capable of handling any foreseeable emergency at the NRL.
3.1 Emergency Organization The emergency organization shall consist of an emergency director and emergency staff acting under the emergency director in accordance with this plan.
The emergency staff shall consist of the staff members of the NRL. The NRL
(
4
- + -,
w -
n.-.--
w
. emergency organintion may be augmented with Radiation Control Office staff and University Police when necessary.
Off-site organintions may be requested to assist the NRL emergency organistion for emergency event response. The assistance and support services provided by these organintions include fire fighting, transportation, hospital facilities, and additional police services. Figure 3 shows the interface between the elements of the emergency organintion. Written agreements with the University Radiation Control Office, Tu: son Fire Department, University Police, ambulance service, and University Hospital are reviewed annually.
3.1.1 Emergency Director The Director of the NRL shall serve as the Emergency Director and shall be in charge of directing emergency operations. He has ultimate authority over on-site activities and personnel. He is responsible for declaring an emergency based on observed action levels or events, for activation of the Emergency Organization, for making protective action decisions, for authorizins radiation exposures to emergency team. members in excess of normal occupational limits, and for declaring the termination of an emergency. Although other persons may provide information and carry out the instructions of the Emergency Director, these responsibilities cannot be dehgated to other persons. The Emergency Director is responsible for assuring the facility is shutdown, for terminating or minimizing releases of radioactive materials, for protecti::g facility personnel and visitors and for assessing severity of an emergency event. To fulfill these responsibilities the Emergency Director shall exercise judgement, and summon assistance as necessary from the University Police, the Radiation Control office, the Arizona Radiation Regulatory Agency, and medical, ambulance, and fire services. If the Director of the NRL is not available to serve, a Senior Reactor Operator (SRO) will assume the responsibilities of the Emergency Director. If SRO cannot serve in this capacity, a reactor operator shall
l l -
I
! assume the duties of Emergency Director and shall immediately ask for assistance
~
from the faculty members of the Department of Nuclear and Energy Engineering.
3.1.2 Emergency Coordinator l
The Reactor Supervisor shall serve as Emergency Coordinator and is responsible for an annual audit of emergency plans and procedures, and updating if necessary.
He is also responsible for emergency training and conducting emergency tests and drills for the operating staff of the NRL in conjunction with the Radiation Control l
Office.
I 3.1.3 Reactor Operator The reactor operator is responsible for the shutdown and securing of the reactor in emergency situations which occur during reactor operstion. He shall make the i
SRO on duty aware of observed action levels and shall take immediate action in case e
of possible reactor damage or a substantial uncontrolled radioactivity release. He shall perform the duties specified for the reactor operstor in the facility operating procedures for emergency evacuation of the reactor room.
{
3.l A NRL Manatement The NRL Management consists of the Director, the Head of the Department of l
Nuclear and Energy Engineering, and the Chairman of the University of Arizona Reactor Committee. One of these individuals will assume responsibility for providios news releases when warranted to the University of Arizona Office of Public Information, which administers all official news releases of the University.
3.1.5 University Office of Public Information The University of Arizona Office of Public Information will handle all official news releases concerning emergency conditions at the NRL.
3.1.6 Radiation Control Office j
The University of Arizona Radiation Control Office (RCO), provides health physics services to the NRL. Professional and technical health physics staff are f-i l
^
i
i 1
1 3
assigned to the NRL as needed, and a Health Physicist from the RCO serves as a member of the University of Arizona Reactor Committee. The Director of Radiation Control shall be notified of any emergency within the NRL, and, when i
k requested, he or his designated alternate shall assist the Emergency Director in evaluating onsite emergency conditions and conducting emergency control measures.
The Director of Radiation Control, or a member of the Radiation Control Office -
staff will determine off-site dose projections and recommend protective measures, j
when warranted, to the Emergency Director.
l 3.1.7 Department Personnel i
i Other individuals on the faculty and staff of the Depanment of Nuclear and Energy Engineering may be assigned duties or responsibilities by the Imergency
[
Director during an emergency.
~
3.1.g University Police The University of Arizona maintains a police force on the campus consisting of
)
commissioned officers, guards, and other personnel. Police services from the Unisersity Police are available at all times. The University Police may be called to I
provide security assistance, emergency rsdio communications, traffic control, and riot control as necessary. Univenity Police officers are instructed in the special i
requirements of the NRL, and a copy of this Emergency Plan is available at the Police Dispatcher's desk. The University Police Dispatcher wi!! arrange for transportation of injured persons to the University Hospital by telephoning the ambulance service with which a support agreement has been made.
3.1.9 Police Dispatcher The University Police Dispatcher provides 24-hour-a-day communication services. Emergency conditions identified by a police officer or police guard are 1
communicated to the Police Dispatcher by radio. Most emergency conditions identified by other persons would be reported on the University emergency j
\\
l l
l
t
- i telephone number, whi:h is answered at the Police Dispatcher's desk. Emergencies identified by NRL operating staff are also reported on the emergency telephone number to the Police Dispatcher. The intrusion alarm is read out at the Police f
Dispat:her's desk. The University Police Dispatcher is responsible for notifi= tion of NRL staff and management in the event of any indication of an emergency condition. Upon request from NRL management or from the Emergency Director, the Police Dispatcher shall also notify the Radiation Control Office and the Arizona Radiation Regulatory Agency. The Police Dispatcher is responsible to notify the l
Tucson Fire Department of a fire emergency, to arrange for an escort from the University entrance to the site of the fire if necessary, and to provide information about local conditions in University buildings.
f
~
3.1.10 Fire Emergency Services The fire emergency services for the University of Arizona are provided by the 1
Tucson Fire Department. The Tucson Fire Department is summoned by the University Police Dispatcher. University Police personnel assigned to work with the 4
Tucson Fire Department on a fire involving potentin! radiation or areas with radioactive materials in the NRL shall inform the fire personnel that the requirements for radiation safety are to be directed by the Emergency Director.
3.1.11 University Hospital The University Hospital, located in the Arizona Health Sciences Center (AHSC),
will provide medical facilities and care for contaminated injured individuals and for individuals suffering from radiation caposure. A training program including principles of radiation safety and contamination control is conducted by the Radiation Control Office for the involved staff of the hospital.
3.1.12 Off-Site Law Enforcement Agencies The City of Tucson Police Department, the Pima County Sheriffs Office and the Arizona Department of Public Safety will provide, if necessary, traffic control
and crowd control at and beyond the campus boundaries within their jurisdieden.
Request for assistance and coordination with these agencies will be through the
{
University Police Department and in accordan:e with the cooperative agreements f
between these agencies.
I i
3.2 Coordination with and Notification of Other Agencies The postulated credible accidents associated with the operation of the Nuclear Reactor Laboratory will not result in a radiological hazard affecting the public health
~
and safety. These emergency events wi!! not require the direct involvement of local, state, and federal agencies. However, these agencies will be notified of emergency conditions as specified below.
3.2.1 US. Nuclear Regulatory Commission The US. Nuclear Regulatory Commission wlU be notified of an emergency as specified by 10CFR20.403 and 20.405. Additionally, the Emergency Director will transmit to the NRC all information specified in part 6.7 of the Technical Specifications to Reactor License R-52.
I l
3.2.2 Arizona Radiation Regulatory Agency The Arizona Radiation Regulatory Agency (ARRA) shall be notified within 15 minutes after identification of Emergency Action Levels corresponding to the emergency class ' Notification of Unusual Event or greater. This notification shall be made by the Police Dispatcher, who sha!! relay the infonnation as specified in the Police Dispatcher procedures.
3.2.3 Local Government Agencies The City of Tucson and Pima County offices will be notified after identification of Emergency Action Levels corresponding to the emergency class
- Notification of Unusual Evenf or greater, and of any incidents which may have mused or threaten to cause an uncontrolled release of radioactive materials that results in a projected off-site dose of 1 Rem whole body or 5 Rem thyroid.
i
~
t
?
I 11 -
~
3 3.2.4 University Department of Risk Management Safety i
j The University of Arizona Department of Risk Management and Safety shall be 4
notified of any emergency involving fire, explosion, or injury of personnel. This i
notification wi!! be done through the University Police Dispatcher.
[
3 3.3 Termination of an Emergency j
The Emergency Director is responsible for declaring the terndnation of an emergency. Prior to termination of an emergency the Emergency director shall l
conclude that no foreseeable subsequent events could cause the action limits of the j
emergency to be exceeded. He will verify that all areas to be reopened to personnel l
)
or the geners! public meet the requirements of 10CFR20 for occupancy. He will l
also confirm that areas to be restricted to entry or which require contro.!!ed access l
are clearly posted.
f 3.4 Authorization for Reentry The Emergency Director shall autWi:e ae.y reentry into the reactor laboratory or portions thereof previously evacuated during an emergency. It shall be the responsibility of the Director of Radiation Control to establish reentry requirements, I
i provide additional personnel monitoring, and insure that protective clothing and
)
proper breathing requipment is utilized if needed.
i 3.5 Authorization of Radiation Exposures in Excess of 10CTR20 Limits With concurrence of the Director of Radiation Control or his designated alternate, the Emergency Director may authorize exposures to emergency team
~
members and radiation workers in excess of normal occupational limits. The exposure limits are 100 Rem whole body for life saving and 25 Rem for corrective actions that mitigate the consequences or reduce the severity of the emergency event.
In either case, the exposure is authorized on a once-in-a-lifetime basis with preference given to the eldest able-bodied volunteers.
v
- v vvv v
y-e-y,,-
,,~
w w--
rm
-y,-w
,y
-=~w..e r -
}
6 12 l
e l
4.0 Emergency Classification System t
i 1
The emergency classes described for the UARR are based upon credible accidents I
associated with NRL operations and other emergency situations that are non-reactor-related i
or have minimal radiological consequences.
4.1 Non-Reactor Safety Reisted Events i
t i
These events are emergencies which do not endanger the public. Advisories to j
i campus police are warranted, and ambulance and medical services may be needed.'
l The following action levels or events will initiate emergency measures associated l
with this emergency class:
i 1.
Civil disturbances or receipt of a bomb threat non-specific to the reactor.
l 2.
Personnel injury with or without radiological complications.
3.
Minor fire or explosion non-specific to the reactor.
7 i
4.
Significant contamination of an individual or of the facility.
l 1
4.2 Notification of Unusual Events i
1 This class of emergency situation will be initiated by' man-made events or 2
j natural phenomena that can be recognized as creating a significant hazard potential that was previously non-existent. There is usually time available to take precautionary and corrective steps to prevent the escalation of an accident or to l
mitigate the consequences should it occur. No releases of radioactive material requiring off-site responses are expected. The emergency wrganization will be.
activated to provide a state of readiness as warranted by the circumstances.
- +
Although the situation may not have caused damage to it,- NRL procedures require -
I 3
f shutdown of the reactor.-
j The following action levels or events will initiate emergency measures associated.
with this emergency class:
i I
mm+
m-w
,ar.,-
wyy.,y y%g
,w 7pgw
.gm, w
y py--y---p._,:-g
=
y.,
m y
q e_,.-.e s-b-,.
e yogp 9m, e
1 i
1 l
13 i
l 1.
Radiological effluents exterior to the Reactor laboratory exceeding 10 MPC-when averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 15 mrem whole body accumulated in 24 4
hours.
o 2.
Receipt of a credible bomb thrett with possible radiological release i
implications.
3.
Fires requiring offsite assistance for control or explosion within the facility.
4.
Failure of a fuel element or failure of an experiment with release of i
i radioactivity as determined by observing the following radiation levels on the facility radiation monitorm (a)
Particulate air monitor. more than 4 x 10-8 microcuries/cc.
i 3
(b)
Area monitort more than 50 mrem / hour for a period of time in exceu i
i of 10 minutes.
I 5.
Pool water level alann and visual observation indicating abnonnal loss of pool water at a rs e exceeding 100 gallons / hour (0.1 meter / hour).
i 4.3 Alert No credible accidents attributable to the reactor or its operation are postulated j
i which can cause emergency conditions beyond t!e operations boundary; therefore,
{
this emergency class is not addressed in this plan.
4.4 Site Area Emergency No credible accidents attributable to the reactor or its opemtion are postulated i
l which can cause emergency conditions beyond the operations boundary; therefore.
i this emergency class is not addressed in this plan.
I e
4.5 General Emergency No credible accidents attributable to'the reactor or its operation are postulated which can cause emergency conditions beyond the operations boundary; ?.herefore, this emergency class is not addressed in this plan.
i 5.0 Emergency Action Levels (EAL's) 3 i
There are no postulated credible accidents associated with the operation of the UARR that lead to exposures exceeding the Protection Action Guides (PAG's) of 1 Rem whole body or 5 Rem thyroid beyond the site boundary. The events or levels specified in L
t
.. N
. = _ -.
l l
I l
Sections 4.1 and da are EAL's for activating the Emergency Organization and initiating i
I protective actions appropriate for the emergency event.
6.0 Emergency Planning Zone The operations boundary for the NRL (defined by rooms 122,124, and 124A in the l
Engineering Building comprising the Nuclear Reactoi Laboratory) is established as the
~
l Emergency Planr.ing Zone (EPZ) for the facility.
j 2
7.0 Emergency Respor.se 7.1 Activation of the NRL Emergency Organization l
The Emergency Director is responsible for initiating the emergency plan and for notifying and mobilizing the emergency organization. During periods of time when the NRL facility is unattended and an unusual situation (lights on at night, alarm i
signal, etc.) is detected by University Police or reported to the University Police Dispatcher, a member of the NRL staff is contacttJ by telephone. The emergency notification list is kept by the Police Dispatcher and copies are posted in the doors l
6 of the b%
The Dispatcher's desk is manned at a!! times insuring that an NRL 1
staff member on the list can be notified. The NRL staff member who is notified l
t shall resolve the situation, and determine whether a real emergency condition exists.
i He shall then inform the Emergency Director, who shall take charge of the
{
t l
emergency, including instructions on steps to be taken before his arrival at the NRL 9
if necessary. Commanication with other emergency support organizations will be made by the Police Dispatcher, either as appropriate for the reported situation, or upon request from the Emergency Director.
7.2 Protective Action Values Because of the low power of the reactor and small potential activity of samples i
irradiated in it, it is likely that all exposures of emergency personnel will be within the limits of 10CFR20 and/or the Protective Action Guidas (PAG's) of 1 Rem whole body or 5 Rem thyroid; however, with the concurrence of the Director of Radiation v
w
~
,, --+.
w y
i f a Control or his delegate, the Emergency Director may authorize exposu e
i of these values to facilitate rescue of injured personnel or take corrective The exposure limit which will mitigate the consequences of the emergency event for life-saving is 100 Rem and 25 Rem for corrective actions. In either if i exposures will be on a voluntary basis and restricted to a once-in-a-l e exposure.
i Radiation Control Office Emergency Response Program 7.3 The Director of Radiation Control or his designated alternate shall be h on-site responsible for determining radiation dose rates and contamiration leve and off-site and will relay this information by face-to-face communicatio i
l nsible for telephone communi-cation, or short wave taclio to the indiv dua respo I
In addition, he will provide for isolation and supervise access accident assessment.
f control to restricted areas to minimize exposures to radiation and the sp I
radioactive contamination.
7.4 Reporting of Emergencies Emergency notification rosters are posted inside and on the outer doo Nuclear Reactor Laboratory and in the University Police Dispatcher's Offii Telephone numbers are listed for NRL personnel, a professional memb l
Radiation Control Office, and the University Police officer responsible for security of the facility. Initial and follow-up emergency messages to th if applicable, to other off-site government agencies should, to the extent k, I
include the following:
Name, title, and telephone number of caller, and the location of the inci 1.
Description of the emergency event and emergency class, 2.
Date and time of incident initiation.
3.
Type of expected or actual release (airborne, waterborne, surface 4.
estimated duration times.
_~
.y_..
r a
s
--ey
l
' 5.
The quantity of radionuclides released or expected to be released.
6.
Projected or actus! dose rates outside the operations boundary.
7.5 Emergency Response for Non-Reactor Safey Related Events 7.5.1 Activation of the Emergency Organization for Non-Reactor Safety Related Events The complete activation of the emergency organization for this emergency class would not normally be required. He Emergency Director will activate that portion of the emergency organization necessary to respond to the event. In any case, NRL Management will be notified.
o 7.5.2 Assessment Actions for Non-Reactor Safety Related Events f
Civil Disturbances or bomb threats shall be assessed by the Emergency Director for niidity using campus police experience and the infor:.ition source.
For personnel injury the Emergency Director shall assess the extent of the injury and whether radioactive contamination is present. Portable radiation monitoring devices a e available in the NRL for this assessment. The assessment will consider the nature of the injury, the appropriate first aid, and the need for l
transportation to medical treatment facilities.
The Emergency Director will assess fire or explosion events to determine the magnitude of the event, the need for prompt control, and the need for support from outside agencies. NRL personnel will monitor the area to determine if radioactive contamination is present. The Radiation Control Office will be informed of any fire or explosion in the NRL whether or not radioactive contamination is dr.ected.
7.5.3 Corrective Actions for Non-Reactor Safety Related Events In the event of a civil disturbance or receipt of a bomb threat non-specific to the reactor, the University Police will be notified and will initiate the appropriate controls to insure the protection of personnel and property. The Emergency Director will notify the Head of the Department of Nuclear and Energy Engineering and keep him informed of the emergency status.
37 For minor fires or explosions non-specific to the reactor or its control system the Reactor Laboratory Director will be notified and NRL staff members may attempt to control the fire with portable fire extinguishers if it is safe to do so. The Tucson Fire Department will be notified by the Police Dispatcher. The Radiation Control Office will be notified of fire in the NRL.
For cases of personnel injury with or without radiological complications, the Emergency Director will determine what medical assistance is needed, and may contact the Police Dispatcher to request transportation. If the injured individual is I
contaminated, decontamination will be attempted only if it is judged that this will not further aggravate the injury. A contaminated injured individual will be transported using contamination control and isolation methods.
l 7.5.4 Protective Actions for Non-Reactor Safety Related Events i
Some protective actions at this level of emergency (e.g., fire alarms) necessitate the evacuation of the Engineering Building. In this case NRL staff members will i
assemble at the west entrance to the Engineering Building to determine if their services are needed. All evacuations will be initiated by sounding the fire alarm and notifying personnel by word of mouth. Should a fire or other event involve areas with radioactive materials, the Emergency Director shall control access to the areas t
y and will be responsible, with support from Radiation Control Office personnel, for the segregation of potentially contaminated pers'onnel.
7.6 Emergency Response for Notification of Unusual Events 7.6.1 Activation of the Emergency Organization for Notification of Unusual Events The Emergency Director will activate that portion of the emergency organization necessary to respond to the emergency situation. In addition, the Head of the l
Department of Nuclear and Energy Engineering and the Director of Radiation l
Control will be kept informed of the emergency status.
i 4
7.6.2 Assessment Actions for Notification of Unusual Events Fuel dunage, experiment failure, or any event manifested by unusual radiation levels within the Reactor Laboratory or the relea's of ernuents at the site boundary sha!! be assessed by the Emergency Director with assistance from available personnel.
Additional support for assessment will be requested from the Radiation Control Office, if needed. The assessment will consist of an observation and evaluation of facility air and/or radiation monitors in the control room and Reactor Room and the use of portable survey instruments. Excessive levels may require evacuation of the Reactor Laboratory and future assessment will be made from the Emergency Support Center (ESC).
A high volume air sampler is available and collected filter paper and swipe samples can be counted in the Counting Laboratory located in Room 120 to identify isotopes. This will be used to assess whether the source is due to fission products, irradiation products, or a non-reactor source.
Civil disturbances and bomb threats shall be assessed by the Emergency Director for n!idity and specificity using campus police experience and the information source.
Explosions and fires in the NRL shall be assessed by the Emergency Director through observation of the affected area and by observation of fire alarms. The Tucson Fire Department may be summoned by the Police Dispatcher. NRL personnel or staff from the Radiation Control Office will monitor the ares to determine if radioactivity is present.
Excessive pool water loss is assessed by the Emergency Director through the low water level alarm, visual observation of the leakage rate, and readings of the reactor area radiation monitors. Leakage which causes the water level to drop quickly will require evacuating the Reactor Room until makeup water can be added.
I i
I l
l.
i i
19
~
7.6.3 Corrective Actions for Notification of Unusual Events If a Notification of Unusual Event is dictated by assessment of high radiation
[
levels, the Resetor Laboratory may be evneunted pending an evaluation and j
identification of the probable source. The Emergency Director, in conference with I
NRL staff and personnel from the Radiation Control Office, shall control access to the Reactor Laboratory until radiation and airborne activity levels have been restored l
to normal.,All personnel who were in the NRL at the time of the emergency will i
be sceounted for. Members of the Reactor Operations staff will assemble at the ESC. Other personnel will assemble in the conference room to be available for assistance.
I For bomb threats with possible radiological release implications, the University j
Police Dispatcher, the Head of the Department of Nuclear and Energy Engineering, and the Radiation Control Office will be notified. The police may initiate controls l
i to insure the protection of personnel and property. The reactor will be shut down l
and personnel may evseuste to the ESC. In case of fire or explosion within the i
i NRL the management will be notified and the Tucson Fire Department will be l
l i
summoned. The Radiation Control Office will be notified of fire in the NRL. In t
l 3
addition, the Emergency Director will assure the reactor is shut down and that i
personnel are evacuated from the Reactor Labomtory. All personnel who were in l
the NRL st the time of fire or explosion will report to the west entrance of the l
Engineering Building to be accounted for. The Emergency Director will monitor the i
extent of the fire and brief fire department personnel upon their arrival.
Pool water loss resulting in excessive radiation levels will require evacuation of l
l personnel from the NRL. Teams will be dispatched by the Emergency Director from ESC to identify the leak as per facility Operating Procedures.
~
i i
I i
I
?
t
. - - ~
4 7.6.4 Protective Actions for Notification of Unusual Events For this emergency class the Reactor Laboratory may be evacuated in accordance with facility Operating Procedures. In such cases, all personnel will be verified present at the ESC, and those individuals who exited the Reactor Laboratory l
will be surveyed for contammation using port; Sie instruments. Those who are l
i contaminated will remain in a room designated by the Emergency Director to await instructions from personnel of the Radiation Control Office. The Emergency Director is responsible for limiting access to the Reactor Room or Reactor l
}
Laboratory to rescue and emergency response operations, j
i The Emergency Director, with support from NRL personnel and staff from the Radiation Control Office, is responsible for minimizing personnel exposure and i
spread of contamination. Emergency exposure levels for personnel shall be in I
accordance with Section 7.2.
i 8.0 Emergency Facilities and Equipment 8.1 Emergency Support Center (ESC) t Room 114 on the first floor of the Engineering Building shall serve as the Emergency Support Center (ESC) for emergency actions. The purp:
of this center is to serve as a control center and accountability station for persons in the area i
-o e
affected by the emergency. The location of the ESC controls access to one hall leading to the NRL and is near the West and North building entrances. Personnel may be assigned from the ESC to the other entrances to the Engineering Building,
[
thus controlling access to the Building and to other halls leading to the NRL. The' l
facility emergency kit is located permanently in the ESC. Telephones are available in the ESC and in adjacent offices which are under control of the department.
I
%2 t ub-I t
4,
8.2 Assessment Facilities The NRL has area radiation monitors with readouts and alarm indications in the i
reactor control room. The Department of Nuclear and Energy Engineering has 1
counting laboratories and portable survey instruments in the Engineering Building.
If necessary, additional counting equipment and survey instruments are available i
from the Radiation Control Office and other University facilities. Both the Department of Nuclear and i.nergy Engineering and the Radiation Control Office m1Intain gamma ray spectro' net'rs for radioisotope identification. A portable high volume air sampler for collection of airborne particulate radioactivity is available in the emergency kit. A pool level alarm indicator and fuel temperature indicator in the control room can provide system or status information for emergency assessment.
g.3 First Aid and Medical Facilities i
Accidents resulting in personal injury without contamination will be handled by administering first aid and summoning an ambulance if needed. In the event of injury requiring medical treatment with contamination, the individua! will be L
transported to the University Hospital, which is located about 0.4 miles from the Engineering Building. Either NRL or RCO personnel will accompany the contaminated injured victim to the hospital, which has emergency procedures for this situation.
\\ ~
Requests for ambulance transport shall be made through the University Police Dispatcher, who will contact the ambulance service with which a support agreement has been made.
l 8.4 Decontamination Facilities Decontamination of personnel at the NRL can normally be handled in the NRL or in the Radiochemistry Laboratory, Room 164, which is across the hall from the NRL. Both laboratories have sinks with soap, paper towels, and contaminated waste containers at hand. In an emergency when the facilities of these laboratories are not available, Room lig, located between the NRL and the ESC, may be used for j
I
f
}
1 i
i I l segregation of contaminated personnel and for decontamination. Radiation Control i
Office penonnel shall be responsible for decontamination of individuals involved in an emergency.
I 3.5 Communications Systems l
l Telephones are located in the NRL Control Room, at the ESC, and elsewhere in j
the Engineering Building, and may be utilized during emergencies. Word-of-mouth l
communications will provide a backup for internal communications. The University f
Police can also be summoned by activation of the intrusion alarm system by pressing a button in the NRL Control Room. University Police maintain a radio system for.
communication between police officers, the dispatcher, and patrol cars.
9.0 Recovery Operations Restoring the NRL to a safe operating condition after an emergency shall be the i
responsibility of the Emergency Director. Operations necessary to restore the facility will be under his~ direction. Radiation Control Office staff sha!! survey, supervise decontamination, and ascertain that contamination and radiation levels within the affected areas are within
{
seceptable limits. The Reactor Laboratory Director shall assess resultant damages, direct l
l repairs and review the emergency. With advice from the Resetor Laboratory Director, the I
University Reactor Committee wi!! authorize continued operation of the reactor.
i I
10.0 Maintaining Emergency Preparedness 10.1 Training f
i NRL operators and staff, and members of the Radiation' Control Office with emergency response responsiblities will complete an initial training ' program and an l
annual review program. For NRL Operators, this may be a part of the Reactor j
Operator Requalification Program.
Specific training in ~ protective action l
decisionmaking will be included in the initial and periodic training for those i
b i
i l
t
_,,. ~.
. ~ _..,
.. ~,. -. -.,...
-U-individuals who may serve as Emergency Director during an emergency. Support l
groups will receive training commensurate with their degree of potential involvement.
10.2 Conduct of Drills and Exercises On-site emergency drills will be conducted annually to test the adequacy of emergency procedures and to ensure that emergency organization personnel are
~
l familiar with their duties. These drills will include the use of appropriate emergency equipment, and will include, as a minimum, testing of the communications links j
with the University Police Department and the Radiation Control Office.
10.3 Critiaues of Drills and Exercises l
l At the conclusion of each drill a critique to identify deficiencies shall be held by the participating NRL staff and observers and may include members of other support and emergency groups. Observer and participant's commenti concerning
?
are:s needing improvement shall be evaluated and consideration given to possible changes in the plan and procedures.
10.4 Emergency Plan Review and Update The Emergency Plan shall be revised and updated as required based on driU results or changes in the facility and shaII be audited annually by the Reactor
.Sup~ervisor. "Dtis audit sha!! be reviewed by the Reactor Committee to ensure the plan is adequate and up-to-date. Letters detailing arrangements with the Radiation Control Office, the University Police, and University Hospital shall be renewed annually, at intervals not to exceed 15 months. Applicable portions of the plan, agreements, and implementing procedures shall be distributed to the University Police, the Radiation Control Ornee, and the Arizona Radiation Regulatory Agency, and any revisions to implementing procedures affected by the plan shall be approved by the Reactor Committee and sent to authorized recipients within 30 days after the revised plans have been issued.
i 1 :
4.
A B
C D
E F
G H
I J
K "J
l [
1 T-I i
li i
i
(
i lI I
i i._{
)
- ^ " * * ' ' ' "
l I
I I
I7 i J i'
'i _:
l]l
- 0. ::.-',*."
1 I
I; I:
I I
i y
's 2 ] D
%.l
!=n~+
m
- ==. :,.~m....
i I
g.
l
=. _ = ~.. -..J.
g
- g p-
- _I_
=
ii EE ::=;
y'9 A 9 G y@
hq 8b
' -J M 3
- = =p.n.
i i
i i
i i e e
i ii E Ef E -
i i
1 1
E
- ===
4
.lill
- = ~,
.J-g i'
i 1 me ae u
w_w-n ::. : =..
I i A.. w a
i I
- == =.
5 f
I 1521 tc._t i
- =.. =m l,
,w7 a
l Fi i
n k..Al L;
lj j
m -
!! $$;'N-Of*i i
. ~
i 5$
I f
- Id-M g
j n = =. =. -
l r-- g n-
~
- ::::2 =::::.
is i
- 2:=
= - -
7
=;
- ==:: :.t.;;;;.
JL_
_)
I f
_l>
1
}
5hh[:.'.,"b.r' '
37 TC Ig.
I
@N C
_. 3 [7 I
i ii.E.*.Y-~'r:=.,':7.;, 8 L;
~~
E eel "E4 At_g I
i g
w
.. -~.
2
!! '::'#.'C. - -. 5 =-%.,e t2 CD L D i!~~"* %.I
- rtGQ I
- = T.::
jqg c==
I
- =. ::.f...
I J
I
" L_1luG
,8=q t
.I. :.
9
-4
,v.
...U~4n
- :=
/::
ii i!'i:.'3". * ". ~ 7 ""~'. -l N@ p~gj I,,,,
t Qg
- =:=. ---
en I
'".e A
--- #
- g =- -3 1>
1 i
%eu N
i
- :=.:=; ::r-a '
i g cm
- =.:-
n.
10 J
J j
V<
o a ->
x i
- ' :: =:~:.::
~~ ~
m
'a 7.o
- =.e=.:=.a.*'
]
f IB 8 a
t-lMlm i
-.O.:r.t.:... - 11 L-
.r-vs:Im_ E._tr.a.m.,E f,,,g
] g q,
- =.= w ~
i
- m..-
- =.~.:'=."
- l a
ji EEf".': ' ~ T*=* 12
' Tc. _MT,W B fD
-id.7k9? %==
- :* */'.'
-. L 5E8 -9 3 h k'hE**.. h 'N lI T g =g:=. =. =::23)] 3 , e q.3 .,"La d M &AC. _2;g Ih i ) t ii E2'7:E E e.~. 14 4] q r~ T li L l- '"i I i i--' 8
- .gp-:e;.;r,.r.. f t F
P { [ ~=' ; *""" "- " 3 I I , a' _ _ m a 1 1, I1 mm a s 4 i . = " - r m' ': 5:"WE 4.I..;-. =. - - - 1 8__; 4 iL J A l di &. 2."'. W".3... 15 l* .f l . n_ !. 1j [---- 4J e,8 fu -a 1 't, 9 I .. ".. ". "*"*""*"'""'lp, l l J l l t T :::"".".'." ::: .I II -I I I.._ J l- ! I l i
- ll".2 t."
=, i r i.
- ". *::" :: 7.'.1"."" "" "
6 !"77":f ~'". '""...
- A *** * ~. ~'" *..
0 t. Tigure 1. UNIVERSITY OF ARIZONA n 2::= #- '-**a
- g. wit:*r.'~j$
.r. u m. CAMPUS MAP m. gs tpure mum m e m. m -- 4 e.e g,,,,, ll::=. ;:.,- .,;..g ::. : suum. - - * - * * = = = = = g s: m- = :r. ~ - - a_._- ".".'."".*'l"..'** y, ; - ss= ~.
t ROBOTICS LABORATORY k ROOM 130 CAMMA RADIATION ROOM 163 LABORATORY QUIPM TORAGE STORAGE ' /gwgs(/ // .(( CLOSET gi, NUCLEAR CHEMISTRY LABORATORY 124 SL CLOSET o NORTH = ~ ROOM 120 COUNTING LABORATORY EMERGENCY PIRINING ZONE (EPZ) SL = DOORS WITH SECURITY IDCES ROOM 118 SCALE: l' = 10*-0* Figure 2. Section of North Wing of the Engineering Building. S
? j Emergency Director i l / Radiation - - - + Control ~ Office l 7 I University Police ^ , _,_ q Police Dispatcher g i l T Management. I ort Director NRL; University Office of l Nuclear & Energy Public Fire Engineering I"f****Ei'" Ambulance Department Head; Hospital Reactor Committee Chairman i W l' 1r e Nuclear & Energy Reactor Operations Engineering Dept. IE*I' Facility Support University Reactor Personnel Co M ttee i i (Authorization for Senior Reactor Operators Faculty operation after an Reactor Operators Clerical emergency) Technical Services Figure 3. NRI. Emergency Organization n v ,e-g e, ,e c, ~ m 1.w-w, -w,.e, e e,-}}